Letter Sequence Approval |
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TAC:MB7497, Missed Surveillance Requirements, Incorporate CEOG Topical Report to Eliminate Pressure Sensor Response Time Testing (Approved, Closed) |
Results
Other: ML021280278, ML022940186, ML030780605, ML031210545, ML031290602, ML031400506, ML031410096, ML031410107, ML031410212, ML031960625, ML032300003, ML032300305, ML032310200, ML032310213, ML032530228, ML032960189
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MONTHYEARML0205206542002-02-25025 February 2002 Order Attachment 1 - Addressee List - Order for Interim Safeguards and Security Compensatory Measures Project stage: Request ML0205002282002-02-25025 February 2002 Issuance of Order for Interim Safeguards and Compensatory Security Measures Project stage: Approval ML0212802782002-05-22022 May 2002 Reply to Response to Order for Interim Safeguards and Security Compensatory Measures Project stage: Other ML0229401862002-10-25025 October 2002 Biweekly Notice Memo, Notice of Consideration, Testing Prestressed Concrete Containment Tendons Project stage: Other ML0302201532003-01-16016 January 2003 Technical Specification Pages for Amendment 215 Missed Surveillances and Adoption of a Technical Specification Bases Control Program Project stage: Acceptance Review ML0229504532003-01-16016 January 2003 Issuance of License Amendment No. 215, Missed Surveillances & Adoption of Technical Specification Bases Control Program Project stage: Approval ML0305902712003-02-26026 February 2003 Technical Specifications, Relocation of TS 3.5(5), Requirements for Testing Prestressed Concrete Containment Tendons to the Updated Safety Analysis Report Project stage: Acceptance Review ML0306307272003-02-26026 February 2003 Issuance of Amendment No. 216, Relocating TS 3.5(5), Requirements for Testing Prestressed Concrete Containment Tendons to the Updated Safety Analysis Report Project stage: Approval ML0305803512003-02-27027 February 2003 Correction to Amendment No. 215 to Fort Calhoun, Station No. 1. Page 5-17 of Technical Specifications Omitted Reference to SR 3.0.5. Corrected TS Page Encl Project stage: Acceptance Review ML0307806052003-03-18018 March 2003 Pressure-Temperature Limit Report Submittal Project stage: Other ML0308402732003-03-24024 March 2003 RAI, Related to Integrated Leak Rate Test Surveillance Interval Project stage: RAI LIC-03-0052, Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request2003-04-10010 April 2003 Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request Project stage: Request LIC-03-0055, Response to Request for Additional Information Integrated Leak Rate Testing Surveillance Interval Amendment Request2003-04-11011 April 2003 Response to Request for Additional Information Integrated Leak Rate Testing Surveillance Interval Amendment Request Project stage: Response to RAI ML0312004872003-04-29029 April 2003 Issuance of Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days Project stage: Approval ML0312105452003-04-29029 April 2003 Tech Spec Pages for Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days Project stage: Other ML0312906022003-05-0808 May 2003 Tech Spec Pages for Amendment No. 218, Administrative and Editorial Changes to FCS TS 1.3 Basis (1); 2.7 (1)a; 2.7 (1)b; 2.7 (1)d; 2.7 (1)i; 2.7 Basis; 3.0.2; Table 3-5, Item 11; and 3.5 (3)ii Project stage: Other ML0312900812003-05-0808 May 2003 Issuance of Amendment No. 218, Administrative and Editorial Changes to FCS TS 1.3 Basis (1); 2.7 (1)a; 2.7 (1)b; 2.7 (1)d; 2.7 (1)i; 2.7 Basis; 3.0.2; Table 3-5, Item 11; and 3.5 (3)ii Project stage: Approval ML0314102122003-05-20020 May 2003 Thesis (Miscellaneous Report - 134 Pages), Fort Calhoun, S107100 Project stage: Other ML0314005062003-05-20020 May 2003 Ltr RELAP5/MOD3.3 Prediction and Model Simulation Project stage: Other ML0314100962003-05-20020 May 2003 Description/Model Simulation (Technical Paper - 5 Pages), Fort Calhoun, S107101 Project stage: Other ML0314101072003-05-20020 May 2003 Listing (Report, Technical - 3 Pages), Fort Calhoun, S107102 Project stage: Other ML0314103762003-05-21021 May 2003 Request for Additional Information Pressure-Temperature Limit Report Submittal (Tac. MB6468) Project stage: RAI LIC-03-0079, Supplemental Response to Request for Additional Information, Integrated Leak Rate Testing Surveillance Interval Amendment Request2003-05-21021 May 2003 Supplemental Response to Request for Additional Information, Integrated Leak Rate Testing Surveillance Interval Amendment Request Project stage: Supplement ML0316800102003-06-17017 June 2003 Request for Additional Information, Use of the Gothic (Version 7.0) Computer Program Project stage: RAI ML0319606252003-07-11011 July 2003 Correction to Amd. 218 for the Fort Calhoun Station, Unit No. 1 (Tac. MB7498) Project stage: Other ML0320202182003-07-18018 July 2003 Ltr Environmental Assessment Relating to Exemption from the Requirements of Appendix G to 10 CFR Part 50 Project stage: Approval ML0320902422003-07-25025 July 2003 Unit 1, License Amendment 219 Modifying Technical Specification 2.1.6 Project stage: Approval ML0321004542003-07-25025 July 2003 Unit 1, Tech Spec Pages for License Amendment 219 Modifying Technical Specification 2.1.6 Project stage: Approval ML0323102002003-08-15015 August 2003 Tech Spec Pages for Amendment No. 221, Use of a Pressure Temperature Limits Report (Ptlr), Change the Minimum Boltup Temperature, Revise the Low Temperature Overpressure Protection (LTOP) Methodology and Analysis Project stage: Other ML0323102132003-08-15015 August 2003 Tech Spec Page to License Amendment No. 220, Grants One-Time Five-Year Extension to Current Ten-Year Test Interval for Containment Integrated Leak Rate Testing Project stage: Other ML0323003052003-08-15015 August 2003 License Amendment No. 221, Use of a Pressure Temperature Limits Report (Ptlr), Change the Minimum Boltup Temperature, Revise the Low Temperature Overpressure Protection (LTOP) Methodology and Analysis Project stage: Other ML0323000032003-08-15015 August 2003 License Amendment No. 220, Grants One-Time Five-Year Extension to Current Ten-Year Test Interval for Containment Integrated Leak Rate Testing Project stage: Other ML0325302282003-09-0404 September 2003 Ft.Calhoun, Closeout Letter - Response to Order for Compensatory Measures Related to Access Authorization Project stage: Other ML0329601892003-10-23023 October 2003 Reply to Response to Order for Fitness-For-Duty Enhancements for Nuclear Security Force Personnel Project stage: Other ML0331002902003-11-0505 November 2003 Unit #1, Issuance of Amendment 222, Authorizing Revisions to the Updated Safety Analysis Report to Incorporate the NRC Approval of the Gothic 7.0 Computer Program for Performing Containment Analysis, (Tac. MB7496) Project stage: Approval 2003-04-10
[Table View] |
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Category:Letter
MONTHYEARML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1282022-08-0303 August 2022 Letter to Victoria Kitcheyan, Chairwoman, Winnebago Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1292022-08-0303 August 2022 Letter to Tiauna Carnes, Chairperson, Sac and Fox Nation of Missouri in Kansas, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1272022-08-0303 August 2022 Letter to Vern Jefferson, Chairman, Sac and Fox Tribe of the Mississippi in Iowa, Re., Ft Calhoun LTP Section 106 ML22138A1232022-08-0303 August 2022 Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 2024-07-08
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements ML20071E1042020-03-25025 March 2020 Issuance of Amendment to Change the Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan to Reflect an ISFSI-Only Configuration ML19297D6772019-12-11011 December 2019 Issuance of Amendment to Revise the Permanently Defueled Technical Specifications to Align to the Requirements for Permanent Removal of Spent Fuel from the Spent Fuel Pool ML18047A6612018-03-28028 March 2018 Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236) ML18068A1652018-03-0909 March 2018 Correction to Page 1 of Attachment to Enclosure 1 for Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML18010A0872018-03-0606 March 2018 Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML17338A1722018-01-19019 January 2018 Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235) ML17276B2862017-12-12012 December 2017 Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036) ML17289A0602017-11-22022 November 2017 Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184) ML17278A6072017-11-17017 November 2017 Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013) ML17165A4652017-07-28028 July 2017 Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437) ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML17179A1782017-06-29029 June 2017 Correction to Technical Specification Definitions - Page 7 for Amendment No. 286, Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and ... LIC-17-0047, Final Request for Additional Information Concerning License Amendment Request 16-07: Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2017-05-15015 May 2017 Final Request for Additional Information Concerning License Amendment Request 16-07: Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme ML17053A0992017-04-0707 April 2017 Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition ML16182A3632016-08-19019 August 2016 Issuance of Amendment No. 289, Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML16139A8042016-06-0808 June 2016 Issuance of Amendment No. 288, Request to Adopt Technical Specifications Task Force (TSTF)-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6b & 6c ML16084A7552016-04-0505 April 2016 Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP ML15307A0132016-02-23023 February 2016 Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML15288A0052015-12-15015 December 2015 Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15209A8022015-08-10010 August 2015 Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML15111A3992015-06-30030 June 2015 Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood ML15035A2032015-03-27027 March 2015 Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors ML15015A4132015-02-20020 February 2015 Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement ML14356A0122014-12-29029 December 2014 Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months ML14328A8142014-12-22022 December 2014 Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3 ML14279A2752014-11-0606 November 2014 Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months ML14209A0272014-08-0707 August 2014 Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis ML14098A0922014-06-16016 June 2014 Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML14003A0032014-01-28028 January 2014 Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13296A5842013-10-25025 October 2013 Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances) ML13203A0702013-07-26026 July 2013 Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances) ML13070A0422013-03-29029 March 2013 Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report ML13043A6612013-02-28028 February 2013 Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits ML1126204022011-09-30030 September 2011 Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications ML1118615712011-08-31031 August 2011 Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c ML1118010942011-07-27027 July 2011 Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1015202962010-06-0202 June 2010 License Amendment, Issuance of Amendment No. 265, Revise Technical Specification 2.15, Table 2-5, Note C for Safety Valve Acoustic Position Indication (Emergency Circumstances) ML1009100772010-05-14014 May 2010 License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e ML0925405912009-10-0909 October 2009 License Amendment, Issuance of Amendment No. 263 Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip ML0919005692009-07-24024 July 2009 Unit No.1 - Issuance of Amendment No. 261, Modify Transformer Allowed Outage Time in Technical Specification 2.7(2) and Delete Associated 2.7(2) Special Reporting Requirements in TS 5.9.3j ML0916205692009-07-24024 July 2009 Issuance of Amendment 262, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0912801022009-07-22022 July 2009 Issuance of Amendment No. 260, Modification of Surveillance Requirements in TS 3.6(3), Containment Recirculating Air Cooling and Filtering System & Removal of License Conditions ML0832606972009-05-12012 May 2009 Issuance of Amendment No. 259, Revise Technical Specifications to Correct Typographical Errors and Make Administrative Clarifications ML0907108912009-03-27027 March 2009 License Amendment, Issuance of Amendment No. 258, Revise Limiting Condition for Operation 2.7(2)j in TS 2.7, Electrical Systems, to Clarify Allowed Outage Time for Emergency Diesel Generators ML0730903612007-12-17017 December 2007 Issuance of Amendment No. 251, Modify Technical Specification Requirements to Support Addition of Safety-Related Swing Inverters to 120 Volt AC Buses ML0720400972007-07-26026 July 2007 Conforming License Amendment to Incorporate the Mitigation Strategies of Commission Order EA-02-026 (Tac No. MD4534) ML0720402832007-07-26026 July 2007 Revised Pages of Facility Operating License DPR-40 to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 ML0706102692007-06-0606 June 2007 Issuance of Amendment No. 250 Adoption of TSTF-447 to Delete Requirements for Hydrogen Purge System - CLIIP 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML24019A1682024-01-31031 January 2024 Safety Evaluation Report for Approval of License Termination Plan ML21271A5992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2 ML20056E4872020-02-26026 February 2020 Staff Review of Fort Calhoun Independent Spent Fuel Storage Installation Physical Security Plan, Security Training and Qualification Plan, and Safeguard Contingency Plan, Revision 0 and the Verification of Additional Security Measures (ASM) ML19297D6742019-12-0909 December 2019 FCS ISFSI Only Tech Specs SER ML18017B0052018-03-30030 March 2018 Review of the Irradiated Fuel Management Plan (CAC No. MF9553; EPID L-2017-LLL-0009) ML18047A6612018-03-28028 March 2018 Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236) ML18010A0872018-03-0606 March 2018 Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML17338A1722018-01-19019 January 2018 Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235) ML17276B2862017-12-12012 December 2017 Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036) ML17263B1982017-12-11011 December 2017 Letter and Safety Evaluation, Request for Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003) ML17289A0602017-11-22022 November 2017 Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184) ML17275A2642017-11-21021 November 2017 Safety Evaluation Input on Fort Calhoun Station Request for Approval of Permanently Defueled Emergency Plan and Emergency Action Level Scheme, Docket No. 50-285 ML17278A6072017-11-17017 November 2017 Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013) ML17165A4652017-07-28028 July 2017 Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437) ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML17144A2462017-06-21021 June 2017 Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management ML17053A0992017-04-0707 April 2017 Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition ML16141A7392016-05-27027 May 2016 Safety Evaluation, Review of Aging Management Program of Reactor Vessel Internals Based on MRP-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines ML16104A0742016-04-15015 April 2016 Relief Request, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI, Fourth 10-Year Inservice Inspection Interval ML16084A7552016-04-0505 April 2016 Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP ML15307A0132016-02-23023 February 2016 Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML16041A3082016-02-19019 February 2016 Relief Requests P-1 - LPSI and CS Pumps; P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21; G-1 - Test Frequency Consistent W/Code Case OMN-20, Fifth 10-Year Inservice Testing Interval ML15288A0052015-12-15015 December 2015 Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15232A0032015-08-21021 August 2015 Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval ML15209A8022015-08-10010 August 2015 Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML15111A3992015-06-30030 June 2015 Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood ML15035A2032015-03-27027 March 2015 Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors ML15015A4132015-02-20020 February 2015 Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement ML14356A0122014-12-29029 December 2014 Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months ML14328A8142014-12-22022 December 2014 Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3 ML14323A5992014-12-0202 December 2014 Relief Request RR-13, Relief from Inservice Testing Requirements to Perform Testing of 4 Valves During the April 2015 Refueling Outage ML14316A1672014-11-19019 November 2014 Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building ML14279A2752014-11-0606 November 2014 Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months ML14209A0272014-08-0707 August 2014 Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis ML14098A0922014-06-16016 June 2014 Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML14003A0032014-01-28028 January 2014 Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13296A5842013-10-25025 October 2013 Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances) ML13203A0702013-07-26026 July 2013 Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances) ML13141A6082013-06-25025 June 2013 Safety Assessment in Response to Request for Information Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13070A0422013-03-29029 March 2013 Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report ML13043A6612013-02-28028 February 2013 Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits ML13017A4672013-01-31031 January 2013 Approval of Request for Change to the Reactor Vessel Surveillance Capsule Removal Schedule ML12333A1192012-12-31031 December 2012 Issuance of Amendment No. 269, Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6) ML1126204022011-09-30030 September 2011 Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications ML1118615712011-08-31031 August 2011 Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c ML1122702902011-08-18018 August 2011 Relief Request RR-12 from Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Fourth 10-Year Inservice Inspection Interval ML1118010942011-07-27027 July 2011 Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1022101332010-08-20020 August 2010 Request for Use of Alternative to Depth-Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds for 4th 10-year Inservice Inspection Interval ML1009100772010-05-14014 May 2010 License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e 2024-01-31
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Text
July 25, 2003 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station, FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT (TAC NO. MB7497)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 219 to Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated January 27, 2003.
The amendment modifies Technical Specification (TS) 2.1.6, "Pressurizer and Main Steam Safety Valves," to increase the "as found pressurizer safety valve (PSV) lift setting tolerances and TS 3.2 (Table 3-5, "Minimum Requirements for Equipment Test") to specify the "as left" PSV setpoint tolerances. The amendment also modifies TS 5.9.1c to remove the requirement to provide a statement in the Monthly Operating Report concerning failures or challenges to power operated relief valves or safety valves.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosures:
- 1. Amendment No. 219 to DPR-40
- 2. Safety Evaluation cc w/encls: See next page
July 25, 2003 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station, FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT (TAC NO. MB7497)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 219 to Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated January 27, 2003.
The amendment modifies Technical Specification (TS) 2.1.6, "Pressurizer and Main Steam Safety Valves," to increase the "as found pressurizer safety valve (PSV) lift setting tolerances and TS 3.2 (Table 3-5, "Minimum Requirements for Equipment Test") to specify the "as left" PSV setpoint tolerances. The amendment also modifies TS 5.9.1c to remove the requirement to provide a statement in the Monthly Operating Report concerning failures or challenges to power operated relief valves or safety valves.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285 DISTRIBUTION:
PUBLIC GHill (2)
Enclosures:
- 1. Amendment No. 219 to DPR-40 PDIV-2 Reading
- 2. Safety Evaluation RidsNrrDlpmLpdiv (HBerkow)
RidsNrrPMAWang cc w/encls: See next page RidsNrrLAEPeyton RidsOgcRp RidsAcrsAcnwMailCenter RidsRgn4MailCenter (AHowell)
SMagruder (NRR/DRIP/RPRP)
WBeckner (NRR/DRIP/RORP)
GHammer (NRR/DE/EMEB)
SSun (Acrs/Acnw)
PKG>: ML032090253 TS: ML032100454 NRR-100
- See previous concurrence ADAMS Accession No.: ML032090242 NRR-058 OFFICE PDIV-2/PM PDIV-2/LA SRXB EMEB OGC Nlo PDIV-2/SC RORP/SC NAME AWang EPeyton SSun
- Uttal SDembek SMagruder DATE 7/7/03 7/3/03 6/16/03 6/16/03 7/14/03 7/17/03 7/16/03 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML032090242.wpd OFFICIAL RECORD COP
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 219 License No. DPR-40
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Omaha Public Power District (the licensee) dated January 27, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-40 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 219, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 25, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 219 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 2-15 2-15 2-15a 2-15a 3-20 3-20 5-7 5-7
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 219 TO FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285
1.0 INTRODUCTION
The current Fort Calhoun Station, Unit 1(FCS) Technical Specification (TS) 2.1.6(1),
"Pressurizer and Main Steam Safety Valves," specifies that "[t]he reactor shall not be made critical unless two pressurizer safety valves are operable with their settings adjusted to ensure valve opening at 2485 psig +1% and 2530 psig +1%." By letter dated January 27, 2003, Omaha Public Power District, (OPPD/licensee), submitted a license amendment request to change TS 2.6.1(1) to "[t]wo pressurizer safety valves shall be OPERABLE in MODES 1 and 2, with lift settings of 2485 psig +1%/-3% and 2530 psig +1%/-3% respectively." The proposed TS amendment would change the lift setting tolerance band for operability of the pressurizer safety valve (PSV) from +1 percent to +1 percent /-3 percent for Modes 1 and 2 to allow for normal setpoint variance. The licensee also proposed to change TS 3.2 (Table 3-5) to specify that following testing of the PSVs, the as-left PSV lift setting tolerance band of +1 percent of their specified setpoint must be met. In addition, the licensee proposed to remove the requirement for a statement in the Monthly Operating Report (MOR) concerning failures and challenges to power-operated relief valves (PORVs) or PSVs.
The licensee stated that the changes to the PSV lift setting tolerances are necessary to minimize TS violations caused by setpoint drift.
2.0 REGULATORY EVALUATION
The requirement of General Design Criterion (GDC) 15 of Appendix A to 10 CFR Part 50 specifies that "[t]he reactor coolant system and associated auxiliary, control, and protection systems shall be designed with sufficient margin to assure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences."
Section 50.36 specifies the Commissions regulatory requirements related to the content of TSs. Specifically, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether a limiting condition for operation (LCO) is required to be included in TSs. These criteria are: (1) installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant system (RCS) pressure boundary; (2) initial plant conditions that are assumed in a design-basis transient and accident analysis; (3) a structure, system or component (SSC) that is used for mitigating consequences of the
design-basis transients and accidents; and (4) an SSC which probabilistic risk assessment has shown to be significant to public health and safety.
NUREG-1432, Revision 2, "Standard Technical Specifications - Combustion Engineering Plants," was developed based on the criteria in 10 CFR 50.36(c)(2)(ii). An SSC which satisfies any of the criteria specified in 10 CFR 50.36(c)(2)(ii) must include an LCO and associated surveillance requirements in the TS. FCS uses the pressurized water reactor of nuclear steam supply systems manufactured by Combustion Engineering Inc. (CE) (now, a part of the Westinghouse Electric Company). PSVs are part of the primary success path and credited in the FCS Updated Safety Analysis Report (USAR) for the transient and accident analysis to mitigate the effects of the design-basis events. In accordance with Criterion 3 of 10 CFR 50.36(c)(2)(ii) discussed above, a TS LCO is required for the PSVs.
The staffs review of the proposed TS changes is based on the compliance with the GDC-15 requirement and consistency with the guidance provided in the standard technical specifications (STS) for the CE-designed plants.
3.0 EVALUATION The staff's review confirmed that the licensees record of the design basis analysis remains valid and acceptable, and the proposed TS changes correctly reflect the results of the acceptable analysis and meet the intent of the applicable sections of the STS for CE-designed plants.
FCS has two spring-loaded PSVs, each installed to operate with a liquid loop seal in the upstream piping. In 1992, the licensee used test data, data from operating events, and an analytical model to evaluate the relationship between PSV lift pressures established with steam (no loop seal) versus expected lift pressure with the installed loop seals. It was found that with the loop seals, the PSVs would initially lift at up to one percent below the steam setting. These circumstances are further discussed in NRC Information Notice 93-02, "Malfunction of a Pressurizer Safety Valve," January 4, 1993. The effect of this setpoint shift due to the presence of the loop seals is discussed below.
The main design purpose of the PSVs is to provide overpressure protection for the RCS.
Together with the reactor protection system, the PSVs ensure that the RCS pressure meets the GDC-15 requirement in terms of the RCS design pressure safety limit (2750 psia). The compliance with the GDC-15 requirement is demonstrated in the analysis of the design basis events. In assessing the effects of the TS changes on the design basis event analysis, the licensee evaluated the existing analysis in the USAR, and identified that the loss-of-load (LOL) event, which results in a highest peak pressurizer pressure, was the case whose consequences were most sensitive to the proposed changes in the PSV setpoint tolerances. The licensee indicated that the analysis of record for the LOL event assumed that the PSVs would open only when the calculated pressurizer pressure reaches the values corresponding to the PSV setpoints with the associated tolerance of +6 percent, which bounds the setpoint tolerance of +1 percent proposed for the PSVs in the TS. The assumed tolerance of +6 percent used in the analysis generates higher effective PSV opening pressures and results in a higher peak pressurizer pressure during an LOL event. Therefore, the staff concludes that the analysis of record for the LOL event remains valid and acceptable for supporting the proposed tolerance of
+1 percent for the PSV setpoints. The licensee stated, and the staff agreed, that the negative
tolerance of -3 percent proposed for the PSV setpoints had no adverse effect on the limiting LOL analysis since the operating PSVs would provide heat sinks for removal of energy from the RCS and use of PSV setpoints with inclusion of negative tolerances (lower effective PSV opening pressures) would result in an earlier opening of the PSVs and decrease the peak pressurizer pressure during overpressurization events such as an LOL event.
In addition, the licensee indicated that the proposed changes do not violate the design basis that requires a reactor trip and power-operated-relief-valve (PORV) actuation before the opening of the PSVs during a pressurization event. The PSV setpoints are designed to be above the high pressurizer pressure reactor trip setpoint that also opens the PORVs.
Specifically, the lowest nominal PSV setpoint is 2500 psia which is 4.1 percent above the TS 1.2 upper limit of 2400 psia for the reactor trip and PORV actuation setting. The margin of 4.1 percent is sufficient to accommodate the combination of the proposed tolerance of
-3 percent for the PSV setpoint and the anticipated 1 percent reduction in actuation pressure due to the loop seal. Therefore, the staff determines that the opening pressures for the PSVs below the high pressurizer pressure setpoint for the reactor trip and PORV actuation are not a concern.
The staff also finds that the changes of the tolerance for the PSV setpoint are within the allowable range specified in NUREG-1432, Revision 2. Specifically, the Bases section of Surveillance Requirement 3.4.10.1 allows a tolerance range of + 3 percent for the PSV setpoint.
Since (1) the proposed changes of the PSV setpoint tolerances are bounded by the analysis of record; (2) they do not violate the design basis that requires a reactor trip and PORV actuation before opening the PSVs during an event that results in an increase in the pressurizer pressure; and (3) the changes of the PSV setpoint tolerance are within the range allowed for the CE-designed plants, such as FCS, as specified in NUREG-1432, Revision 2, the staff concludes that the proposed changes of the PSV setpoint tolerances are acceptable.
The licensee also proposes to remove from TS 5.9.1c the requirement for a statement in the MOR concerning failures or challenges to PORVs or PSVs. The licensee states that when there is such a challenge or failure, this statement typically refers the reader to a Licensee Event Report (LER) for details of the event. The requirements for submitting LERs would not be affected by the proposed change to TS 5.9.1c. The staff also notes that NRC Generic Letter 97-02, "Revised Contents of the Monthly Operating Report," which was issued for the general purpose of requesting the submittal of less information in the MOR, does not require a statement in the MOR concerning failures or challenges to PORVs or PSVs. Further, the staff has not identified a reason, unique to FCS, for retaining this requirement; therefore, the staff concludes that the licensees proposal to remove the requirement for a statement in the MOR regarding failures or challenges to PORVs or PSVs is acceptable.
The licensee proposed to revise TS 3.2, Table 3-5, Item 3 to require an "as-left" PSV setting tolerance of +/-1 percent. Setting the PSV to this tolerance helps reduce the overall setpoint drift over time, which is acceptable to the staff.
The licensee also proposed other changes to items (2), (3) and (4) of TS 2.1.6. They involve changes of the defined terms in TS 2.1.6. Currently the defined terms appear in lowercase text
and the licensee proposed to convert them to uppercase text for consistency with the STS.
These are editorial changes and have no effect on the Limiting Conditions for Operation, Actions and Surveillance Requirements of the TS. Therefore, they are acceptable.
The staff has evaluated the licensees request to amend the FCS TS to increase the tolerance band of the lift settings of the PSVs. The changes are intended to minimize TS violations caused by setpoint drift. Based on the evaluation discussed in Sections 2.0 and 3.0, the staff finds that the proposed changes of the PSV setpoint tolerances are bounded by the analysis of record, and are within the allowable range specified in the STS for the CE-designed plants.
Therefore, the staff concludes that the licensees amendment request is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (68 FR 12956). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). This amendment also involves changes in recordkeeping, reporting or administrative procedures or requirements. Accordingly, with respect to these items, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: G. Hammer S. Sun Date: July 25, 2003
Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn Iowa Department of Public Health ATTN: James R. Curtiss, Esq. 401 SW 7th Street, Suite D 1400 L Street, N.W. Des Moines, IA 50309 Washington, DC 20005-3502 Mr. Richard P. Clemens Chairman Division Manager - Nuclear Assessments Washington County Board of Supervisors Omaha Public Power District P.O. Box 466 Fort Calhoun Station Blair, NE 68008 P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. John Kramer, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Sue Semerera, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Cententiall Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. John B. Herman Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee Bureau of Radiological Health